Radiation Safety Information Computational Center

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Package Name Abstract RSICC Tapelist Title
1DB-2DB-3DB Abstract
Document 		C00741 PC586 00 One-Dimensional Diffusion Code System for Nuclear Reactor.
1DX Abstract
Document 		P00096 I0360 00 A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections.
1DX Abstract
Document 		P00096 U1108 00 A One-Dimensional Diffusion Code System for Producing Energy Group Collapsed and Self-Shielded Cross Sections.
3DDT Abstract
Document 		C00605 C6600 00 Multigroup Diffusion Code System for Use in Fast Reactor Analysis.
ABAREX Abstract
Document 		P00248 MNYCP 01 Neutron Spherical Optical-Statistical Model Code System.
ABBN-90 Abstract
Document 		D00182 MNYCP 00 Multigroup Constant Set for Calculation of Neutron and Photon Radiation Fields and Functionals, Including the CONSYST2 Program.
ABLEIT-TRANS Abstract
Document 		P00247 C0175 00 Error Propagation Analysis for Burnup Calculation.
ACAB-2008 Abstract
Document 		C00758 MNYCP 00 ACtivation ABacus Inventory Code System for Nuclear Applications.
ACAT Abstract
Document 		P00257 FM380 00 Monte Carlo Simulation of Atomic Collisions in Amorphous Targets in the Binary Collision Approximation.
ACDOS3 Abstract
Document 		C00442 C7600 00 Calculation of Activities and Dose Rates Produced by Neutron Activation.
ACFA Abstract
Document 		C00478 I3033 00 A Versatile Activation Code for Coolant and Structural Materials.
ACOH Abstract
Document 		C00191 I3675 00 Aerojet COHORT Monte Carlo Code System.
ACORNS Abstract
Document 		P00264 IBMPC 01 Analysis of Correlations Used in Neutron Spectrometry.
ACRA-II Abstract
Document 		C00213 I0360 00 Kernel Integration Code System for Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident.
ACRA-TRIT Abstract
Document 		C00283 I0360 00 The Tritium Version of ACRA-II, Estimation of Radiation Doses Caused by a Hypothetical Reactor Accident.
ACRO Abstract
Document 		C00354 I0360 00 Calculation of Organ Dose from Acute or Chronic Inhalation and Ingestion of Radionuclides.
ACT-ARA Abstract
Document 		C00372 CYXMP 00 Code System for the Calculation of Changes in Radiological Source Terms with Time.
ACTIV-PC Abstract
Document 		P00287 IBMPC 00 A Program to Process Gamma or X-ray Spectra.
ACTIV87 Abstract
Document 		D00169 ALLCP 00 Fast Neutron Activation Cross Section File.
ACTL82 Abstract
Document 		D00069 ALLCP 01 Evaluated Neutron Activation Cross-Section Library.
ACTV-F/H Abstract
Document 		D00155 ALLCP 00 Neutron Activation Cross Section Library for Fusion Reactor Design.
ACTV-FUS/INT Abstract
Document 		D00170 ALLCP 00 International Library of Neutron Activation Cross-Section Data for Fusion Reactor Application.
ADASAGE Abstract
Document 		P00426 IBMPC 00 Ada Application Development System, Versions 4.02, 4.0 and 3.1.
ADEFTA 4.0 Abstract
Document 		P00543 MNYCP 00 Atomic Densities for Transport Analysis Script.
ADENA Abstract
Document 		P00190 C0000 00 Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
ADENA Abstract
Document 		P00190 I3033 00 Code System for Application of Adjusted Data in Calculating Fission-Product Decay Energies and Spectra.
ADJMOM Abstract
Document 		C00212 I3675 00 Adjoint Moments Method Gamma-Ray Transport Code System.
ADLER III Abstract
Document 		P00058 I0360 00 A Program to Calculate Cross Sections from Adler-Adler Resonance Parameters.
ADO Abstract
Document 		C00189 I3675 00 Aerojet Discrete Ordinates Calculational System.
AGDATA Abstract
Document 		D00127 I0360 00 Two Agricultural Production Data Libraries (AGDATC and AGDATG) for Dose and Risk Assessment Models.
AIR DATA Abstract
Document 		D00014 I0360 00 Sample Input to ANISN for Calculation of Neutron and Secondary Gamma-Ray Transport in Air.
AIRBORNE Abstract
Document 		C00263 I0360 00 Airborne Contaminants Dispersion Code.
AIRDIF Abstract
Document 		C00360 C6600 00 A Two-Dimensional Atmospheric Radiation Diffusion Code.
AIRDOS-PC Abstract
Document 		C00551 IBMPC 00 Clean Air Act Compliance Software for Personal Computers. See C00542/CAP-88.
AIREM Abstract
Document 		C00242 I3691 00 Calculation of Doses, Population Doses, and Ground Depositions Due to Atmospheric Emissions of Radionuclides.
AIRFEWG Abstract
Document 		D00049 I0360 00 Results of ANISN Multigroup Calculations of Gamma-Ray, Neutron, and Secondary Gamma-Ray Transport in Infinite Homogeneous Air Using DLC-31/(DPL-1/FEWG1) Cross Sections.
AIRGAMMA Abstract
Document 		C00567 FM380 00 A Program For The Calculation Of External Exposure To Gamma Rays From A Radioactive Cloud.
AIRSCAT Abstract
Document 		C00341 DP010 00 Calculation of Dose Rate for Gamma-Rays Scattered in Air.
AIRTRANS Abstract
Document 		C00110 I3675 00 Monte Carlo Time and Energy-Dependent Three-Dimensional Radiation Transport Code.
AISITE II Abstract
Document 		C00286 I0360 00 Reactor Siting Code System.
AKERN Abstract
Document 		C00190 C0000 00 Aerojet Point Kernel Integration Calculational System.
AKERN Abstract
Document 		C00190 U1108 00 Aerojet Point Kernel Integration Calculational System.
AKTIV Abstract
Document 		C00339 I0360 00 An Evaluation of Activity, Afterheat and Biological Hazard Potential of Stainless Steel Structures in Fusion Reactor Blankets.
ALARA 2.7.8 Abstract
Document 		C00723 MNYCP 00 Code System for Analytic and Laplacian Adaptive Radioactivity Analysis.
ALARM-B2 Abstract
Document 		P00218 I0360 00 A Computer Code System for Analysis of a Large Break LOCA of a BWR.
ALBEDO-DATA Abstract
Document 		D00224 MNYCP 00 KSU Neutron Albedo Data.
ALBEMO Abstract
Document 		C00268 C6600 00 Albedo Monte Carlo Code System.
ALDOSE Abstract
Document 		C00577 IBMPC 00 Dose Calculation for Alpha Disc Source.
ALGAM-97 Abstract
Document 		C00152 I3675 00 Monte Carlo Estimation of Internal Dose from Gamma-Ray Sources in a Phantom Man.
ALICE-2008 Abstract
Document 		P00550 PC586 00 Statistical Model Code System to Calculate Particle Spectra from HMS Precompound Nucleus Decay.
ALKASYS-PC Abstract
Document 		C00558 IBMPC 00 A Computer Program For Studies of Rankine-Cycle Space Nuclear Power Systems.
ALPHA-M Abstract
Document 		P00169 I0360 00 Least-Squares Resolution of Gamma-Ray Spectra in Environmental Samples.
ALPHN Abstract
Document 		C00612 IBMPC 00 Code System for Calculating (alpha,n) Neutron Production in Canisters of High-Level Waste.
ALPS Abstract
Document 		P00144 F2307 00 Alpha Spectrum Analysis Code System.
AMARA Abstract
Document 		P00079 I3675 00 Nuclear Data Adjustment Using Lagrange's Multipliers Method.
AMC Abstract
Document 		C00090 I3675 00 Monte Carlo Albedo Code for Neutron and Capture Gamma-Ray Distributions in Rectangular Concrete Ducts.
AMPX 77 Abstract
Document 		P00315 CY000 00 Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B.
AMPX-77 Abstract
Document 		P00315 ALLMF 01 Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B.
AMPX01 Abstract
Document 		D00027 I3675 02 126-Group Coupled Neutron and Gamma-Ray Transport Cross-Section Data Generated by AMPX.
AMUSE Abstract
Document 		P00028 C6600 00 Gamma-Ray Spectra Unfolding Code.
ANA Abstract
Document 		P00356 IBMPC 00 Code System for Gamma-Ray Spectra Analyses.
ANIPLO D50 Abstract
Document 		P00213 I0360 00 A Digital Computer Program for Plotting Results from Calculations with the Sn Computer Program ANISN.
ANISN-ORNL Abstract
Document 		C00254 MNYCP 02 One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering.
ANISN-PC Abstract
Document 		C00514 IBMPC 00 Multigroup One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering. RSIC recommends CCC-650/DOORS3.2a for most applications.
ANITA-2000 Abstract
Document 		C00693 MNYCP 00 Code System to Calculate Isotope Inventories from Neutron Irradiation for Fusion Applications.
ANITA-4 Abstract
Document 		C00606 MNYCP 01 Analysis of Neutron Induced Transmutation and Activation. See ANITA-2000 (CCC-693).
ANL-BPB Abstract
Document 		M00004 MNYCP 00 Argonne National Laboratory Code Center: Benchmark Problem Book.
ANS643 Abstract
Document 		D00129 IBMPC 02 ANS-6.4.3 Geometric Progression Gamma-Ray Buildup Factor Coefficients.
ANSIFT Abstract
Document 		P00077 C6600 00 ANSI Standard Fortran Sifting Program.
ANSIFT Abstract
Document 		P00077 I0360 00 ANSI Standard Fortran Sifting Program.
ANSL-V Abstract
Document 		D00154 ALLCP 01 ENDF/B-V Based Multigroup Cross Section Libraries for Advanced Neutron Source (ANS) Reactor Studies.
ANTE 2 Abstract
Document 		C00131 I3675 00 Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry.
APARNA-II Abstract
Document 		C00296 I0360 00 Integral Transport Theory Code System Based on Discrete Ordinate Representation in Space and Direction-Slab Geometry.
APPLE-2 Abstract
Document 		P00111 FM200 00 Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates.
APPLE-2 Abstract
Document 		P00111 I3081 00 Plotter of Neutron and Gamma-Ray Spectra and Reaction Rates.
APSAI Abstract
Document 		P00065 I3691 00 Activity Calculations and Plotting of Neutron or Gamma-Ray Spectra Generated by Discrete Ordinates Code System ANISN.
APUD 3.0 Abstract
Document 		C00637 IBMPC 00 Code System for Analyzing, Predicting Consequences of, and Guiding the Response to Nuclear Emergencies.
ARC Abstract
Document 		C00224 C6600 00 Aircraft Radiation Transport Code System, Crew Dose Calculation.
ARCON96 Abstract
Document 		C00664 IBMPC 00 Code System to Calculate Atmospheric Relative Concentrations in Building Wakes.
AREAC Abstract
Document 		C00438 I3033 00 Radiological Emission Analysis Code System.
AREAD Abstract
Document 		P00088 I0360 00 Input Data Processor for Transport Codes.
ARMYL-G Abstract
Document 		C00297 U1106 00 Calculation of Transmission Factors for Gamma Rays from Nuclear Explosions.
ARMYL-N Abstract
Document 		C00298 U1106 00 Calculation of Transmission Factors for Neutrons from Nuclear Explosions.
ARRRG Abstract
Document 		C00404 U1100 00 Calculation of Radiation Dose to Man from Radionuclides in the Environment.
ASFIT-VARI Abstract
Document 		C00336 H0000 00 Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ASFIT-VARI Abstract
Document 		C00336 IBMPC 00 Gamma-Ray Transport Code System for One-Dimensional Finite Systems.
ASOP Abstract
Document 		C00126 IRISC 00 Multigroup One-Dimensional Discrete Ordinates Transport Code System for Shield Optimization.
ASTROS Abstract
Document 		C00073 I7090 00 Calculation of Primary and Secondary Proton Dose Rates in Spheres and Slabs of Tissue.
AT123D Abstract
Document 		C00417 I0360 00 Analytical Transient One-, Two-, and Three-Dimensional Simulation of Waste Transport in an Aquifer System.
ATHENA_2D Abstract
Document 		P00431 MNYCP 00 Code System For Simulation Of Hypothetical Recriticality Accidents in a Thermal Neutron Spectrum.
ATM-TOX Abstract
Document 		C00472 I3033 00 An Atmospheric Transport Model for Toxic Substances.
ATTOW-KB Abstract
Document 		C00132 I0370 00 Multigroup Two-Dimensional Removal-Diffusion (Spinney Method) Shielding Code System.
AUS98 Abstract
Document 		C00519 MNYWS 01 Modular System for Neutronics Calculations of Fission Reactors, Fusion Blankets, and Other Systems.
AUTOJOM-JOMREAD Abstract
Document 		P00008 C6600 00 Computer Programs to Generate or Check Coefficients for Quadratic Equations Describing 3D Geometries.
AXMIX Abstract
Document 		P00075 CYXMP 00 ANISN Cross Section Code System.
AXMIX Abstract
Document 		P00075 IRISC 01 ANISN Cross Section Code System.
AXMIX-PC Abstract
Document 		P00297 IBMPC 00 ANISN Cross Section Mixing Code System.
BABEL Abstract
Document 		D00104 I3033 00 Multi-Purpose Neutron and Gamma-Ray Cross Section Library for Fast Reactor Shielding Design.
BALTORO Abstract
Document 		C00479 C6600 00 Code for Coupling of Monte Carlo and Discrete Ordinates Radiation Transport Calculations.
BARC-35 Abstract
Document 		D00124 IBMMF 00 35-Group Neutron Cross Sections and Resonance Self-Shielding Factors Generated in ISOTXS and BRKOXS Format from ENDF/B-IV Using MINX.
BASACF Abstract
Document 		P00285 IBMPC 00 Bayesian Approach to Spectrum Adjustment with Covariance Filter.
BAYES Abstract
Document 		P00205 DP010 00 User's Guide for A General-Purpose Computer Code System for Fitting a Functional Form to Experimental Data.
BCG Abstract
Document 		C00578 C0170 00 A Code For Calculating Pointwise Neutron Spectra and Criticality in Fast Reactor Cells.
BEACON MOD3 Abstract
Document 		P00402 CDCMF 00 Code System for Thermal-Hydraulic Analysis of Nuclear Reactor Containments.
BEBC Abstract
Document 		C00077 I7090 00 Electron Bremsstrahlung Penetration Code for Space Vehicles.
BED Abstract
Document 		C00078 I7090 00 Electron Penetration Code for Space Vehicles.
BERMUDA Abstract
Document 		C00616 FV260 03 Discrete Ordinates Code System for Shielding Analysis for Use with Fusion and Fission Reactors.
BETA II Abstract
Document 		C00117 C6600 00 Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BETA II Abstract
Document 		C00117 I0360 00 Monte Carlo Bremsstrahlung and Electron Transport Analysis in Geometry.
BFR
US DISTRIBUTION ONLY 		Abstract
Document 		P00449 C0176 00 Code System for Common Cause Failure Data Analysis.
BIGGI Abstract
Document 		C00066 I3675 00 Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P &4T.
BIGGI Abstract
Document 		C00066 U1108 00 Numerical Gamma-Ray Transport Code for Plane or Spherical Multilayer Geometry, Versions 3P and 4T.
BISON 1.5 Abstract
Document 		C00464 HM200 00 A One-dimensional Discrete Ordinate Transport and Burnup Calculation Code. (Burnup of Isotopes and One-Dimensional Transport).
BISON-C Abstract
Document 		C00659 MNYWS 00 One-Dimensional Discrete Ordinate Transport and Burnup Calculation Code System.
BLOCKAGE V2.5R Abstract
Document 		P00377 IBMPC 00 Code System to Calculate Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in a BWR.
BLT-FEMWATER
US DISTRIBUTION ONLY 		Abstract
Document 		C00633 PC386 00 Code System to Solve for Release and Transport of Contaminants through Saturated/Unsaturated Media.
BMC-MG Abstract
Document 		C00291 C6600 00 Multigroup Monte Carlo Neutron and Gamma-Ray Shielding Code System for Plutonium.
BOB-7 SERIES Abstract
Document 		P00084 F2306 00 Theory and Use of Gamma-Ray Spectrum Analysis Codes for Ge(Li) Detectors.
BOLD VENTURE IV Abstract
Document 		C00459 I3033 00 A Reactor Analysis Code System.
BON Abstract
Document 		P00173 I0360 00 A Code System for Unfolding Multisphere Spectrometer Neutron Measurements.
BPPC Abstract
Document 		C00076 I7090 00 Proton Penetration Codes for Space Vehicles.
BREESE-II Abstract
Document 		P00143 I3033 00 Auxiliary Routines for Implementing the Albedo Option in the MORSE Monte Carlo Code System.
BREMRAD Abstract
Document 		C00031 I7090 00 External and Internal Bremsstrahlung Calculation Code.
BRHGAM Abstract
Document 		C00350 I3033 00 Monte Carlo Estimation of Absorbed Dose from X-Ray Sources in Phantom Man.
BRMSTK Abstract
Document 		P00044 C6600 00 CSEWG Integral Data Testing Shielding Experiment Code System.
BRMSTK Abstract
Document 		P00044 I3691 00 CSEWG Integral Data Testing Shielding Experiment Code System.
BSPRP2 Abstract
Document 		P00372 IRISC 00 Code System to Process DORT Boundary-Flux Files.
BUCORST Abstract
Document 		P00339 PC386 00 A Code to Prepare Burnup-Dependent Multigroup Nuclear Reactor Source Terms.
BUGLE-80 Abstract
Document 		D00075 PC386 01 Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-80 Abstract
Document 		D00075 IBMPC 02 Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-80 Abstract
Document 		D00075 IBMPC 03 Coupled 47 Neutron, 20 Gamma-Ray Group, P3, Cross Section Library for LWR Shielding Calculations by the ANS-6.1.2 Working Group on Multigroup Cross Sections. We recommend ENDF/B-VI derived data in DLC-185/BUGLE-96.
BUGLE-96 Abstract
Document 		D00185 ALLCP 00 Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications.
BULK_C-12 Abstract
Document 		C00738 PC586 00 Code System to Estimate Neutron and Photon Effective Dose Rates from Medium Energy Protons or Carbon Ions Through Concrete or Concrete/Iron.
BURP-2 Abstract
Document 		C00237 C6600 00 Calculation of Buildup and Decay of Radioactive Fission Products.
BUSH Abstract
Document 		C00333 I0360 00 A Code to Calculate Radiation Doses Inside Buildings from Routine Releases of Radionuclides to the Atmosphere.
BWR-LTAS Abstract
Document 		C00485 I3033 01 Code System for Boiling Water Reactor Long-Term Accident Simulation.
CAAC Abstract
Document 		C00476 D0VAX 00 Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. See CCC-542/CAP-88.
CAAC Abstract
Document 		C00476 I3033 00 Code System for Implementation of Atmospheric Dispersion Assessment Required by the Clear Air Act. See CCC-542/CAP-88.
CACA-2 Abstract
Document 		C00302 I0360 00 Heavy Isotope and Fission-Product Concentration Calculation Code System.
CAD Abstract
Document 		D00059 I0360 00 51 Neutron, 25 Gamma-Ray Group ALBEDO DATA Generated with DOT for Various Materials.
CALKUX Abstract
Document 		C00594 IBMPC 00 Code System to Calculate Exposure Transmission of Medical X-ray Beams Through Barrier Materials.
CALOR95 Abstract
Document 		C00610 MNYWS 00 Monte Carlo Code System for Design and Analysis of Calorimeter Systems, Spallation Neutron Source (SNS) Target Systems, etc.
CAMERA Abstract
Document 		C00240 C0074 00 Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CAMERA Abstract
Document 		C00240 IBMPC 01 Radiation Transport Analysis Code System and the Computerized Man (CAM) Model.
CANDULIB-AECL Abstract
Document 		D00210 MNYCP 00 Burnup-Dependent ORIGEN-S Cross Section Libraries for CANDU Reactor Fuel Characterization.
CAP-88 Abstract
Document 		C00542 D0VAX 00 Clean Air Act Assessment Package.
CAP-88 Abstract
Document 		C00542 I3090 00 Clean Air Act Assessment Package.
CAP88-PC Abstract
Document 		C00542 IBMPC 01 Clean Air Act Assessment Package.
CAPS-2 Abstract
Document 		C00074 CDCMF 00 Analysis of Structures for Fallout Radiation Shielding.
CARL-2.2 Abstract
Document 		C00743 PC586 00 Code System to Calculate Radiotoxicity, Activity, Dose and Decay Power Calculations for Spent Fuel.
CARMEN SYSTEM Abstract
Document 		C00487 U1110 00 A Code System for Neutronics PWR Calculation by Diffusion Theory with Space-Dependent Feedback Effects.
CARNAC Abstract
Document 		C00238 I3691 00 Calculation of Flux and Neutron Spectra in the Case of Criticality Accident.
CARP-82 Abstract
Document 		P00131 I3033 00 Multigroup Albedo Data Using DOT Angular Flux Results.
CARSTEP Abstract
Document 		C00024 I7090 00 Trajectory and Environment Code-Electron and Proton Fluxes Impinging on Spacecraft in Orbit.
CASCADE Abstract
Document 		C00176 C6600 00 Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CASCADE Abstract
Document 		C00176 I0360 00 Monte Carlo Simulation of the Transport of High Energy Electrons and Photons in Matter.
CASIM Abstract
Document 		C00265 I0360 00 Monte Carlo Simulation of Transport of Hadron Cascades in Bulk Matter.
CASK Abstract
Document 		D00023 I3691 04 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CASK-81 Abstract
Document 		D00023 I0370 05 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CASK-81 Abstract
Document 		D00023 IBMPC 06 22 Neutron, 18 Gamma-Ray Group, P3, Cross Sections for Shipping Cask Analysis.
CASKCODES Abstract
Document 		P00262 IBMPC 00 CAPSIZE, SCOPE, AND KWIKDOSE for Shipping Cask Optimization, Dose Calculation, Parameter Evaluation, and Shielding Requirements.
CASTHY Abstract
Document 		P00316 F0230 00 Statistical Model Calculation for Neutron Cross Sections and Capture Gamma-Ray Spectra.
CAVEAT Abstract
Document 		C00169 I3675 00 General Purpose Monte Carlo Time-Dependent Radiation Transport Code in Complex Geometry.
CCRMN Abstract
Document 		P00366 MNYCP 00 Monte Carlo Simulation of the Coupled Transport of Electrons and Photons.
CDR Abstract
Document 		C00182 C6600 00 A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape.
CDR Abstract
Document 		C00182 I0360 00 A Constant Dose Range Code System, Using the LANL-NWEF Neutron-Gamma-Ray Air Flux Tape.
CEAR-PPU Abstract
Document 		P00528 PC586 00 Code System for Monte Carlo Simulation of Detector Pulse Pile Up.
CECP-BWR Abstract
Document 		P00370 PC386 00 Estimating Boiling Water Reactor Decomissioning Costs.
CECP-PWR Abstract
Document 		P00371 PC386 00 Estimating Pressurized Water Reactor Decomissioning Costs.
CEM03.01 Abstract
Document 		P00532 MNYCP 00 Monte-Carlo Code System to Calculate Nuclear Reactions in the Framework of Improved Cascade-Exciton Model.
CEMENT 1.02
US DISTRIBUTION ONLY 		Abstract
Document 		P00412 IBMPC 00 Computer Code System for the Estimation of Long-Term Performance of Cement-Based Materials.
CEPXS/ONELD 1.0 Abstract
Document 		C00544 MNYCP 02 One-Dimensional Coupled Electron-Photon Multigroup Discrete Ordinates Code System.
CERPI-CEREL Abstract
Document 		P00147 I0360 00 Code Systems for Automatic Analysis of Gamma-Ray Spectra Obtained with Ge(Li) Detectors.
CGS 11.4 Abstract
Document 		P00243 MFMWS 03 Common Graphics System, Version 11.4.
CHAINS-PC Abstract
Document 		C00604 IBMPC 00 Code System to Compute Atom Density of Members of a Single Decay Chain.
CHAINT-MC Abstract
Document 		C00584 CYXMP 00 A Two-Dimensional Model for the Analysis of Contaminant Transport in a Fractured Porous Medium.
CHARGE II Abstract
Document 		C00070 C6500 00 Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHARGE II Abstract
Document 		C00070 I3675 00 Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHARGE-PC Abstract
Document 		C00070 IBMPC 00 Space Radiation Shielding Code - Proton and Electron Penetration of Multilayered Slabs and Spheres.
CHENDF 7.02 Abstract
Document 		P00333 MNYCP 05 Codes for Handling ENDF/B-V and ENDF/B-VI Data.
CHNSED Abstract
Document 		C00671 I0360 00 Code System to Model Sediment & Containment Transport.
CITATION-LDI 2 Abstract
Document 		C00643 PC386 02 Nuclear Reactor Core Analysis Code System.
CLAW-IV Abstract
Document 		D00036 I0360 02 Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations.
CLAW-IV Abstract
Document 		D00036 I3033 03 Coupled 30 Neutron, 12 Gamma-Ray Group Cross Sections Based on ENDF/B-IV for Radiation Transport Calculations.
CLEAR Abstract
Document 		D00042 I3691 00 126 Neutron, 36 Gamma-Ray Cross Sections in AMPX and CCCC Interface Formats for LMFBR Neutronics Calculations.
CLOUD-M Abstract
Document 		C00032 I3565 00 Gamma-Ray Dose Rate from a Radioactive Cloud-Kernel Integration Code.
CNCSN Abstract
Document 		C00726 PC586 00 One, Two- and Three-Dimensional Coupled Neutral and Charged Particle SN Code System.
COAG-II Abstract
Document 		P00070 I0360 00 Calculation of the Westcott Epithermal Index and the Westcott 2200 m/s Neutron Flux.
COBB Abstract
Document 		D00016 I3675 01 123-Group Neutron Cross Section Data Generated from ENDF/B-II Data for Use in the XSDRN Discrete Ordinates Spectral Averaging Code.
COBRA-EN Abstract
Document 		P00507 IBMPC 00 Code System for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Cores.
COBRA-SFS CYCLE 3 Abstract
Document 		P00472 MNYCP 00 Code System for Thermal Hydraulic Analysis of Spent Fuel Casks.
COBRA4I Abstract
Document 		P00419 MNYCP 00 Code Sytem to Calculate Rod-Bundle and Core Thermal-Hydraulics.
CODAC (2) Abstract
Document 		P00073 I0360 00 For TIMOC 72, Monte Carlo Three-Dimensional Neutron Transport Code's Data Generator.
COGAP Abstract
Document 		P00375 MNYCP 01 Nuclear Power Plant Containment Hydrogen Control System Evaluation Code.
COHORT-II Abstract
Document 		C00198 I7094 00 General Purpose Monte Carlo Radiation Transport Code System.
COLLIMATOR Abstract
Document 		C00136 I7090 00 Monte Carlo Calculation of the Spectrum of Gamma Radiation from a Collimated Co-60 Source.
COLUMN2 Abstract
Document 		C00534 ALLMF 00 Calculation of Effects of Physicochemical Processes on Migration.
COMAND Abstract
Document 		P00091 I0360 00 A Multigroup ANISN Cross Section Data Library Collapsing Code System.
COMBINE-PC Abstract
Document 		P00286 IBMPC 00 Code System to Compute Neutron Spectra and ENDF/B Version 5 Based Multigroup Neutron Constants.
COMIDA Abstract
Document 		P00343 MNYCP 00 Radionuclide Food Chain Model for Acute Fallout Deposition.
COMMIX-1B
US DISTRIBUTION ONLY 		Abstract
Document 		P00393 DVX11 00 3-D Single-Phase Thermal Hydraulics
COMMIX-1B
US DISTRIBUTION ONLY 		Abstract
Document 		P00393 I3033 00 3-D Single-Phase Thermal Hydraulics
COMMIX-1C
US DISTRIBUTION ONLY 		Abstract
Document 		P00393 MNYCP 00 3-D Single-Phase Thermal Hydraulics
COMNUC3B Abstract
Document 		P00302 CYXMP 00 A Compound Nucleus Analysis Program.
COMPAR Abstract
Document 		P00240 C0170 00 Compares Multigroup Cross Sections Generated by NJOY, GROUPIE, FLANGE-II, ETOG-3 and XLACS.
COMPARE-MOD1A Abstract
Document 		P00410 C7600 00 Transient Flow W/Sinks & Doors
COMPARE-MOD1A Abstract
Document 		P00410 I3033 00 Code System to Calculate Transient Flow With Heat Sinks & Doors.
COMPASS 1.0.0 Abstract
Document 		P00520 PC586 00 Computerization of MARSSIM for Planning and Assessing Site Surveys.
COMPBRN3 Abstract
Document 		P00389 PC386 00 Code System for Modeling Compartment Fires.
COMPLOT Abstract
Document 		P00259 IBMMF 00 Convert EXFOR Format Data to Computation Format and Plot Comparisons of EXFOR and ENDF/B Evaluated Data (Version 86-1).
COMPRASH Abstract
Document 		C00072 I3675 00 Spinney Removal-Diffusion Shielding Code.
COMRADEX4 Abstract
Document 		C00332 I0360 00 Evaluator of Potential Radiological Doses in the Near (< 10 km) Environment of Radioactive Release.
CONDOS-II Abstract
Document 		C00416 I0360 00 Code for Estimating Radiation Doses from Radionuclide-Containing Consumer Products.
CONFOLD Abstract
Document 		P00053 C6600 00 Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra.
CONFOLD Abstract
Document 		P00053 I0360 00 Least-Structure Unfolding Code System for Measured Neutron and Gamma-Ray Spectra.
CONSTRIP V Abstract
Document 		C00139 I3675 00 Vertical Barrier-Finite Source Plane Gamma-Ray Penetration Code System.
CONTEMPT-LT28B
US DISTRIBUTION ONLY 		Abstract
Document 		P00387 C7600 00 Code System to Predict Containment Pressure-Temperature Response To a Loss-Of-Coolant Accident.
CONTEMPT4 Abstract
Document 		P00397 MNYCP 00 Code System for PWR & BWR Multicompartment Containment Analysis, Versions MOD5 & MOD6.
CONVERT Abstract
Document 		P00036 C6600 00 An IBM-to-CDC Program Conversion Code.
COOL-C Abstract
Document 		P00017 I0360 00 Spectra Unfolding Codes.
CORTES Abstract
Document 		P00404 I0360 00 Code System for Thermal & Mechanical Analysis of Tees.
COVERV Abstract
Document 		D00077 I0360 01 Compilation of Multigroup Cross-section Covariance Matrices in COVERX Format for Several Important Materials (Generated from ENDF/B-V Data using PSR-093/PUFF2).
COVERX Abstract
Document 		D00044 I0360 02 Compilation of Multigroup Cross-Section Covariance Matrices in COVERX Format for Several Important Materials.
COVFILS Abstract
Document 		D00091 I0360 00 A 30-Group Covariance Library Based on ENDF/B-V.
COVFILS-2 Abstract
Document 		D00137 ALLCP 00 Neutron Data and Covariances for Sensitivity and Uncertainty Analysis.
CRAC2 Abstract
Document 		C00419 C0000 00 Code System for Calculating Reactor Accident Consequences.
CRAC2 Abstract
Document 		C00419 I3033 00 Code System for Calculating Reactor Accident Consequences.
CRECTJ5 Abstract
Document 		P00250 D0780 00 A Computer Program for Compilation of Evaluated Nuclear Data in ENDF/B Format.
CRESO Abstract
Document 		P00184 I3081 00 Resonance Data-Handling Code System.
CRRIS Abstract
Document 		C00518 I3033 00 Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides.
CRRIS Abstract
Document 		C00518 PC586 00 Computerized Radiological Risk Investigation System for Assessing Doses and Health Risks from Atmospheric Releases of Radionuclides.
CRRS Abstract
Document 		P00376 DALPU 01 Conference Room Reservation System.
CRYSTAL BALL Abstract
Document 		C00233 C6600 00 Code System for Determining Neutron Spectra from Activation Measurements.
CRYSTAL BALL Abstract
Document 		C00233 I0360 00 Code System for Determining Neutron Spectra from Activation Measurements.
CTR DATA Abstract
Document 		D00028 I3675 01 73-Group P3 Coupled Neutron and Gamma-Ray Cross Sections for Fusion Reactor Calculations.
CUPED Abstract
Document 		P00032 I3675 00 Scintillation Spectrometer Polyenergetic Gamma Photon Experimental Distributions Unfolding Code.
CYGAS Abstract
Document 		C00317 I3033 00 A Gamma-Ray Attenuation Code System for Large Gamma-Ray Sources Shielded by Coaxial Cylinders.
CYGNUS-C SPHERE Abstract
Document 		C00232 I0360 00 Monte Carlo Neutron Transport Code System in Spherical Geometry.
CYLDOS Abstract
Document 		C00389 I0360 00 A Cylindrical Geometry Gamma-Ray Flux Attenuation Code System.
D2O Abstract
Document 		P00398 PC486 00 Code System for Computing Thermodynamic and Transport Properties of D2O.
DABL69 Abstract
Document 		D00130 I0360 01 Defense Nuclear Applications Broad-Group Library based on ENDF/B-V in ANISN Format.
DACRIN Abstract
Document 		C00273 U1100 00 Airborne Radionuclide Organ Dose Calculational System.
DANCOFF-MC Abstract
Document 		P00509 MNYCP 00 Code System for Monte Carlo Calculation of Dancoff Factors in Irregular Geometries.
DANCOFF3 Abstract
Document 		P00279 D8810 00 Calculates Dancoff Correction.
DANTE Abstract
Document 		P00185 I0370 00 Unfolding Code System for Energy Spectra Evaluation for Dosimetry Purposes.
DASH-FP Abstract
Document 		C00366 C0000 00 A One-Dimensional Analytic-Numerical Solution to the Problem of Multicomponent Time-Dependent Diffusion of Fission Products.
DASQHE Abstract
Document 		P00278 D8810 00 Calculates Dancoff Corrections Factors.
DATINIT Abstract
Document 		P00258 DGMV1 00 Interactive Program To Access Photon Interaction Data.
DAVE Abstract
Document 		C00166 I3675 00 Monte Carlo Gamma-Ray Transport Code System in One-Dimensional Spherical Geometry.
DCHAIN 1.3 Abstract
Document 		C00640 MNYCP 01 Code System for Radioactive Decay and Reaction Chain Calculations.
DCHAIN-SP2001 Abstract
Document 		C00712 MNYWS 01 Code System for Analyzing Decay and Build-up Characteristics of Spallation Products.
DCHAIN2 Abstract
Document 		C00370 PC486 00 A Code System for Calculation of Transmutation of Nuclides.
DCTDOS Abstract
Document 		C00520 IBMPC 00 Neutron and Gamma-Ray Penetration in Composite Duct Systems.
DDXCODES Abstract
Document 		C00583 FM380 00 One-, Two- and Three-Dimensional Transport Codes Using Multigroup Double-Differential Form Cross Sections.
DDXLIB Abstract
Document 		D00123 FM380 01 125-Neutron Group Double Differential Cross Section Library.
DECAYREM Abstract
Document 		D00030 I0360 02 Radioactive Decay Spectra in EXREM Format.
DECDC 1.0 Abstract
Document 		D00213 MNYCP 00 Nucear Decay Data Files for Radiation Dosimetry Calculations.
DEIS Abstract
Document 		C00455 C6600 00 Draft Environmental Impact Statement on Licensing Requirements for Land Disposal of Radioactive Waste.
DELFIC-TES Abstract
Document 		C00257 I3033 00 Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud.
DELFIC-TES Abstract
Document 		C00257 U1108 00 Multigroup Kernel Integration Code System for Calculating Gamma-Ray Exposure from a Radioactive Airborne Cloud.
DEMON & DEMON R Abstract
Document 		C00181 I3675 00 Demonstration Monte Carlo Code System in Slab Geometry.
DENIS Abstract
Document 		P00082 I0360 00 Monte Carlo Simulation of the Capture and Detection of Neutrons with Large Liquid Scintillators.
DEPLETOR Abstract
Document 		P00523 MNYCP 00 Code System to Provide Depletion Capability to the U.S. NRC PARCS Code
DETAN 95 Abstract
Document 		P00361 MNYCP 00 Code System to Calculate Spectrum-Averaged Cross Sections and Detector Responses in Neutron Spectra.
DIAMANT2 Abstract
Document 		C00414 PC386 00 Multigroup Two-Dimensional Discrete Ordinates Transport Code System for Triangular Geometry, Release 2.0.
DIF3D8-VARIANT8 Abstract
Document 		C00649 MFMWS 01 Code System Using Variational Nodal Methods and Finite Difference Methods to Solve Neutron Diffusion and Transport Problems.
DIFBAS Abstract
Document 		P00334 MNYCP 00 A Bayesian Approach to Unfolding a Neutron Spectrum from a Spectrum of Recoiled Protons.
DIFMOD Abstract
Document 		C00572 I3083 00 A Computer Program To Calculate The Leaching of Radionuclides and the Corrosion of Cemented Waste Forms in Water or Brine.
DIMEN Abstract
Document 		P00341 IBMPC 00 Code System for Isotope Identification by Gamma-Ray Analysis.
DINT Abstract
Document 		P00049 C6600 00 Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
DINT Abstract
Document 		P00049 I0360 00 Multigroup Coherent-Incoherent Cross Section Data Generator for Photon Transport Calculations.
DINT-YAEC Abstract
Document 		C00306 ALLMF 00 Evaluator of I1 and I2 Integrals as Used in Long-Term External Gamma-Ray Doses from Routine Atmospheric Releases.
DIPHO Abstract
Document 		C00140 I3675 00 Monte Carlo Gamma-Ray Code System-Infinite Medium, Mono-energetic and Isotropic Point Source.
DISDOS Abstract
Document 		C00170 I0360 00 Calculation of Dose Distribution in Human Phantoms Irradiated by External Photon Sources.
DISKTRAN Abstract
Document 		C00533 CYXMP 00 Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data.
DISKTRAN Abstract
Document 		C00533 I3033 00 Dose Calculations at Detectors from the End of a Cylinder Using DOT IV Scalar Flux Data.
DISPERS Abstract
Document 		C00454 MNYCP 00 Mathematical Models for Dispersion of Radionuclides
DKR Abstract
Document 		C00323 CY000 00 A Radioactivity and Dose Rate Calculation Code System for Fusion Reactors.
DLS Abstract
Document 		C00264 C6600 00 Two-Dimensional Shielding Calculational System with Diffusion Theory and Line-of-Sight Method.
DOMINO Abstract
Document 		P00064 I0360 00 A General Purpose Code System for Coupling Discrete Ordinates and Monte Carlo Radiation Transport Calculations.
DOMINO-II Abstract
Document 		P00162 I3033 00 General Purpose Code System for Coupling DOT-IV Discrete Ordinates and Monte Carlo Radiation Transport Calculations.
DOMUS Abstract
Document 		P00301 IPCXT 00 A Program for Decomposing A Two-Dimensional Spectrum.
DOORS 3.2A Abstract
Document 		C00650 MFMWS 04 One, Two- and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System.
DOPEX Abstract
Document 		C00177 I3675 00 Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEX Abstract
Document 		C00177 U1108 00 Laminated Shield Weight Optimization Code System-Steepest Descent Calculational Model.
DOPEX-1D2C Abstract
Document 		C00214 I0360 00 A One-Dimensional, Two-Constraint Radiation Shield Optimization Code System.
DOQDP Abstract
Document 		P00110 I0360 00 Discrete Ordinates Quadrature Generator.
DORGLIB Abstract
Document 		P00181 I0360 00 An Interactive Program for Displaying Nuclide Decay and Generation Data Based on ORIGEN Data Library.
DORIAN Abstract
Document 		P00425 IBMPC 00 Code System to Implement Bayes Method for Plant Aging Risk Analysis.
DOSCOV Abstract
Document 		D00090 I0360 00 24-Group Covariance Data.
DOSDAM77-81 Abstract
Document 		D00081 C6400 00 620 Group, SAND-II Formatted, Neutron Cross Sections Based on ENDF/B-IV and Other Sources for Spectral, Integral, and Damage Analyses.
DOSDAM81-82 Abstract
Document 		D00097 C0000 00 Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
DOSDAM84 Abstract
Document 		D00131 IBMMF 00 Multigroup Cross Sections in SAND-II Format for Spectral, Integral, and Damage Analyses.
DOSDAT II-81 Abstract
Document 		D00079 I0370 00 Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOE Abstract
Document 		D00144 ALLMF 00 Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSDAT-DOE Abstract
Document 		D00144 IBMPC 01 Dose-Rate Conversion Factors for External Exposure to Photons and Electrons.
DOSE 1 Abstract
Document 		C00165 I3675 00 Gamma-Radiation Dosimetry for Arbitrary Source and Target Geometry.
DOSE-SGTR Abstract
Document 		C00624 IBMPC 00 Code System to Calculate the Integrated Iodine Release to the Environment During a Steam Generator Tube Rupture in a PWR.
DOSFACTER II Abstract
Document 		C00400 D0750 00 Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DOSFACTER II Abstract
Document 		C00400 I0360 00 Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DOSFACTER-DOE Abstract
Document 		C00536 I3033 00 Calculation of Dose-Rate Conversion Factors for Exposure to Photons and Electrons.
DPCT Abstract
Document 		C00580 CYXMP 00 A Deterministic-Probabilistic Model For Contaminant Transport.
DPL-400 GEDT1 Abstract
Document 		D00031 I0360 08 Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-401 NEDT Abstract
Document 		D00031 I0360 09 Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402A/GPDT1 Abstract
Document 		D00031 I0360 10 Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DPL-402B/GPDT1 Abstract
Document 		D00031 I0360 11 Defense Nuclear Agency 37 Neutron, 21 Gamma Ray Coupled, P3, Multigroup Library in ANISN Format.
DRAGON3.05D Abstract
Document 		C00647 MNYWS 03 Lattice Cell Code System.
DRALIST Abstract
Document 		D00080 ALLCP 00 Radioactive Decay Data for Application to Radiation Dosimetry and Radiological Assessments.
DSNQUAD Abstract
Document 		P00251 IPCXT 00 Calculates Angular Quadrature Weights and Cosines.
DTF-69 Abstract
Document 		C00130 C6600 00 One-Dimensional Multigroup Photon Transport Discrete Ordinates Code System.
DTF-INDIA Abstract
Document 		C00458 I0370 00 Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IV Abstract
Document 		C00042 C6600 00 Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-IV MODIFIED Abstract
Document 		C00042 I0370 00 Multigroup Neutron Transport Discrete Ordinates Code System with One-Dimensional, Anisotropic Scattering.
DTF-TRACA Abstract
Document 		C00412 U1100 00 One-Dimensional Multigroup Neutron Transport Discrete Ordinates Code System.
DTK Abstract
Document 		C00223 I3675 00 One-Dimensional Multigroup Neutron Transport Code System.
DUFOLD Abstract
Document 		P00042 I0360 00 Derivative Unfolding Code - Determination of Neutron Spectra from NE-213 Pulse Height Data.
DUST Abstract
Document 		C00453 I3033 00 Albedo Monte Carlo Simulation of Neutron Streaming Through Multilegged Ducts.
DUST-BNL Abstract
Document 		C00634 PC386 00 Disposal Unit Source Term by One-Dimensional, Transient, Finite-Difference, Subsurface Release and Transport of Contaminants.
DWBA07/DWBB07 Abstract
Document 		P00338 MNYCP 01 Code System for Inelastic and Elastic Scattering with Nucleon-Nucleon Potential
DWNWND Abstract
Document 		C00383 DP010 00 Interactive Gaussian Plume Atmospheric Transport Model.
DWUCK-CHUCK Abstract
Document 		P00546 MNYCP 00 Nuclear Model Code System for Distorted Wave Born Approximation and Coupled Channel Calculations.
E-DEP-1 Abstract
Document 		C00275 D0VAX 00 Heavy Ion Energy Deposition Code System.
E3LWR Abstract
Document 		D00098 C0000 00 45 Neutron, 16 Gamma-Ray and 15 Neutron, 5 Gamma-Ray Group LWR Cross Section Libraries Derived from EURLIB-III using the AGRUKO Optimized Collapsing Scheme.
ECIS-06 Abstract
Document 		P00227 MNYCP 01 Code System to Solve the Coupled Differential Equations Arising in Nuclear Model Calculations.
ECPL82 Abstract
Document 		D00106 ALLCP 00 Evaluated Charged-Particle Data Library.
EDISTR Abstract
Document 		P00191 I3033 00 Prepares a Nuclear Decay Data Base for Internal Radiation Dosimetry Calculations.
EDITOR Abstract
Document 		P00035 I0360 00 Alters Mode, Copies, Merges, Punches, Edits, or Adds to ENDF/B-Formatted Data on Tapes or Cards.
EDMULT 6.4 Abstract
Document 		C00430 MNYCP 02 Evaluates Electron Depth-Dose Distributions in Multilayer Slab Absorbers.
EDNA Abstract
Document 		C00104 I7090 00 Electron Dose and Number Analysis Code by Kernel Integration.
EDO Abstract
Document 		C00489 U1110 00 A Code System in Fortran V for the Evaluation of Dose During Normal Operation of a Nuclear Power Plant.
EDSFI
US DISTRIBUTION ONLY 		Abstract
Document 		D00215 PC486 00 Electrical Distribution System Functional Inspection Data Base.
EEDB Abstract
Document 		P00531 MNYCP 00 The Energy Economic Data Base.
EFDOS Abstract
Document 		C00411 I0360 00 Calculation of Effective Committed Dose Equivalents by Inhalation of Radioactive Materials Occurring in Routine Atmospheric Releases from Nuclear Fuel Cycle Facilities.
EGAD Abstract
Document 		C00206 I0360 00 Calculation of Dose from External Gamma-Ray Emitters.